Te-Chuan Wang

发表

Numerical investigation on the influence of the type of PI controller combined with MAAP code on the steady-state performance of a nuclear power plant

Te-Chuan Wang, Cheng-Lun Yu, Cheng-Lun Yu, 2019, Nuclear Engineering and Design.

Analysis of Severe Accident Management Strategy for a BWR-4 Nuclear Power Plant

Jyh-Tong Teng, Te-Chuan Wang, J. Teng, 2005 .

RPV Depressurization Strategy Analysis for Chinshan Nuclear Power Plant by Using MAAP5

Te-Chuan Wang, Yu-Huai Shih, 2016 .

A real-time computer graphical user interface for Advanced Boiling Water Reactor case comparison using MAAP software

Yuan-Hsiang Chang, Yu-Chen Chen, Te-Chuan Wang, 2010, 2010 International Computer Symposium (ICS2010).

Simulation of a PWR Reactor Vessel Level Indicating System during Station Blackout with MELCOR 1.8.5

J. Teng, Te-Chuan Wang, S. Wang, 2006 .

Simulation of Maanshan TMLB' sequence with MELCOR 1.8.3

Te-Chuan Wang, S. Wang, C. Chien, 1999 .

Uncertainty Quantification Using the MAAP5 Code of In-Vessel Hydrogen Generation in a Severe Accident at an Advanced Boiling Water Reactor

M. Lee, Te-Chuan Wang, 2020, Nuclear Technology.

Localization and size estimation for breaks in nuclear power plants

Shun-Chi Wu, Yuh-Ming Ferng, Te-Chuan Wang, 2021, Nuclear Engineering and Technology.

Deep learning schemes for event identification and signal reconstruction in nuclear power plants with sensor faults

Shun-Chi Wu, Te-Chuan Wang, Ting-Han Lin, 2021 .

Comparison of Severe Accident Results among SCDAP/RELAP5, MAAP, and MELCOR Codes

Jyh-Tong Teng, Te-Chuan Wang, J. Teng, 2005 .